Preliminary Leak-before Break Assessment of Intermediate Heat Transport System Hot-Leg of a Prototype Generation IV Sodium-cooled Fast Reactor (소듐냉각고속로 원형로 중간열전달계통 고온배관의 파단전누설 예비평가)
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- Transactions of the Korean Society of Pressure Vessels and Piping
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- v.12 no.1
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- pp.126-133
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- 2016